As a flexible, cost-effective energy alternative to large scale nuclear power reactors, this book examines the potential future use of small modular reactors for the generation of electricity in different regions. Exploring advanced nuclear technologies, chapters describe the current situation and perspective of the small modular reactors market (SMRs) in different regions around the word, including North and South America, Europe, Asia, Middle East and Africa. Particular attention is paid to the benefits of using these types of reactors for the generation of electricity, discussing their efficiency and reduced construction time, as well as exploring the main difficulties encountered in the development stage. Looking at the potential dangers that SMRs pose to the environment and population, the text presents the new safety measures that have been adopted in SMRs design to reduce future risk.

This book is a compilation of selected papers from the 3rd International Symposium on Software Reliability, Industrial Safety, Cyber Security and Physical Protection of Nuclear Power Plants, held in Harbin, China on 15th-17th August 2018. The symposium discussed the status quo, technical advances and development direction of digital instrument control technology, software reliability, information security and physical protection in the process of nuclear power development. Offering technical insights and know from leading experts, this book is a valuable resource for both practitioners and academics working in the field of nuclear instrumentation, control systems and other safety-critical systems, as well as nuclear power plant managers, public officials, and regulatory authorities.

This thesis deals with the problem of ion confinement in thermonuclear fusion devices. It is a topic of general interest, as it helps to understand via numerical simulations the ion confinement properties in complex geometries, in order to predict their behavior and maximize the performance of future fusion reactors. The main work carried out in this thesis is the improvement and exploitation of an existing simulation code called ISDEP. This code solves the so-called ion collisional transport in arbitrary plasma geometry, improving in this sense other existing codes. Additionally, it presents outstanding portability and scalability in distributed computing architectures, such as Grid or Volunteer Computing. The main physical results can be divided into two blocks. First, the study of 3D ion transport in ITER is presented. ITER is the largest fusion reactor (under construction) and most of the simulations so far assume the axis-symmetry of the device. Unfortunately, this symmetry is only an approximation because of the discrete number of magnetic coils used. ISDEP has shown, using a simple model of the 3D magnetic field, how the ion confinement is affected by this symmetry breaking. Secondly, ISDEP has been applied successfully to the study of fast ion dynamics in fusion plasmas. The fast ions, with energies much larger than the thermal energy, are a product of the device's heating system. Thus, a numerical predictive tool can be used to improve the heating efficiency. ISDEP has been combined with the FAFNER2 code to study such ions in stellarator (TJ-II, LHD) and tokamak (ITER) geometries. It has also been validated by experimental results. In particular, comparisons with the CNPA diagnostic in the TJ-II stellarator are remarkable.

This book examines the different spatial control techniques for regulation of spatial power distribution in advanced heavy water reactors (AHWR). It begins with a review of the literature pertinent to the modeling and control of large reactors. It also offers a nodal-core model based on finite difference approximation since the AHWR core is considered to be divided into 17 relatively large nodes. Further, it introduces a nonlinear model characterizing important thermal hydraulics parameters of AHWR and integrates it into the neutronics model to obtain a coupled neutronics-thermal hydraulics model of AHWR. The book also presents a vectorized nonlinear model of AHWR and implements it in MATLAB/Simulink environment. The model of the reactor is then linearized at the rated power and put into standard state variable form. It is characterized by 90 states, 5 inputs and 18 outputs. Lastly, it discusses control techniques for a nonlinear model of AHWR. This book will prove to be a valuable resource for professional engineers and implementation specialists, researchers and students.

Separation technologies are of crucial importance to the goal of significantly reducing the volume of high-level nuclear waste, thereby reducing the long-term health risks to mankind. International co-operation, including the sharing of concepts and methods, as well as technology transfer, is essential in accelerating research and development in the field.

The writers of this book are all internationally recognised experts in the field of separation technology, well qualified to assess and criticize the current state of separation research as well as to identify future opportunities for the application of separation technologies to the solution of nuclear waste management problems. The major emphases in the book are research opportunities in the utilization of innovative and potentially more efficient and cost effective processes for waste processing/treatment, actinide speciation/separation methods, technological processing, and environmental restoration.

This book of proceedings collects the papers presented at the workshop on "Diagnostics for Experimental Fusion Reactors" held at Villa Monastero, Varenna (Italy) September 4-12, 1997. This workshop was the seventh organized by the International School of Plasma Physics "Piero Caldirola" on the topic of plasma diagnostics and the second devoted to the diagnostic studies for the International Thermonuclear Experimental Reactor (ITER). The proceedings of the first workshop on ITER diagnostics were published by Plenum Press in 1996 with the title "Diagnostics for Experimental Thermonuclear Fusion Reactors." While many of the ideas and studies reported in the first workshop remain valid, there has been sub stantial progress in the design and specification of many diagnostics for ITER. This moti vated a second workshop on this topic and the publication of a new book of proceedings. ITER is a joint venture between Europe, Japan, Russia and USA in the field of con trolled thermonuclear fusion research. The present aim of ITER is to design an experimental fusion reactor that can demonstrate ignition and sustained burn in a magnetically confined plasma. To achieve this goal, a wide range of plasma parameters will have to be measured reliably. It is also anticipated that diagnostics will be used much more extensively as input to control systems on ITER than on present fusion devices and this will require increased relia bility and long-term stability."

Developing a nuclear power programme is a major undertaking requiring careful planning and preparation. This publication provides guidance for Member States that with to assess the resources required for the development of the infrastructure needed for a nuclear power programme. Resource estimates are presented in person years, to account for economic differences across countries, in terms of labour costs, which may vary significantly. The data are presented in sufficient detail that they can also be used by countries that have decided to expand their nuclear programme after a long period without building any new nuclear power plants.

Requirements for the safe transport of radioactive material are established in IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition. Packages intended for the transport of radioactive material have to be designed to meet applicable national and international regulations. For package designs that require approval by a competent authority, the documentary evidence of compliance with the applicable regulations is commonly known as package design safety report (PDSR). For package designs that do not require competent authority approval, a PDSR would also be an appropriate form of documentary evidence of compliance with the Transport Regulations. This Safety Guide provides recommendations on the preparation of a PDSR to demonstrate compliance of a package design for the transport of radioactive material with the Transport Regulations. This Safety Guide is intended for use by applicants for approval of package designs (when package designs are subject to competent authority approval) as well as by package designers and/or consignors (when package designs do not require competent authority approval). Regulators will benefit from the common structure for the competent authority assessment process, and designers and consignors will find a consistent approach to justify the compliance of a package design with the regulatory requirements.

In September, 1999, with the generous support of NATO, scientists from 18 different nations gathered in Katsiveli, Yalta, Ukraine at the NATO Advanced Research Workshop on Hydrogen Materials Science and Chemistry of Metal Hydrides to present their research and to discuss world energy problems and possible solutions, interactions of hydrogen with materials, the role of hydrogen in materials science, and the chemistry of metal hydrides. High level and highly professional presentations were accompanied by a great deal of discussion and debate of the issues from both fundamental and global perspectives. The result was a large number of new collaborations, new directions, and better understanding of energy and materials issues. The research presented at this meeting can be found in this volume. These papers range from global perspectives such as the new vision of energy and how hydrogen fits into that future, to reviews such as a look at nickel hydride over the last 40 years, to very specific current research. A large number of papers are included on hydrogen and materials. These papers include articles on properties such as superconductivity, diffusion EMF, magnetic properties, physico chemical properties, phase composition, and permeability as a result of the interaction with or incorporation of hydrogen. Also included are papers discussing the use of hydrogen as a processing or alloying agent. The use of hydrogen in the synthesis of battery electrode materials, composite materials, and alloys is also presented."

While many books are available on disaster medicine, none is specifically devoted to the role of physicians in the management of patients exposed to radiation leakage from a damaged nuclear power plant. "Radiation Disaster Medicine" aims to fill this void based on the response to the Fukushima nuclear accident. Each chapter addresses principles and practices of radiation medicine within the specific context of that accident. Topics covered include the role of physicians in radiation disasters, the concepts of external and internal exposure, prehospital and hospital response, disaster behavioral health, and radiation emergency response from the perspective of national and international institutions. Most of the contributors are active educators and researchers in radiation medicine with first-hand experience in dealing with prehospital triage and management of patients within secondary and tertiary care hospitals in Japan.

Safety of VVER-440 Reactors endeavours to promote an increase in the safety of VVER-440 nuclear reactors via the improvement of fission products limitation systems and the implementation of special non-destructive spectroscopic methods for materials testing. All theoretical and experimental studies performed the by author over the last 25 years have been undertaken with the aim of improving VVER-440 defence in depth, which is one of the most important principle for ensuring safety in nuclear power plants. Safety of VVER-440 Reactors is focused on the barrier system through which the safety principle is organised: * nuclear fuel matrix; * fuel cladding; * integrity of primary circuit; and * confinement system. All these barriers are described in detail and are compared to European standards. Industrial engineers will find Safety of VVER-440 Reactors a useful guide to the safe operation of nuclear power plants and it is an informative source of information for researchers in both industry and academia. Employees of related governmental and regulatory organisations may also benefit from reading this book.

Market: Scientists and students involved in thermonuclear fusion research. Thermonuclear fusion research using the confinement device tokamak represents one of the most prominent science projects in the second half of the 20th century. International Tokamak Community is now committing significant effort and funds to experiments with burning plasma, hot and dense enough to produce significant nuclear fusion reactions. The methods used to enhance tokamak performance have a profound and immediate effect on machine design. This book provides an up-to-date account of research in tokamak fusion and puts forward innovative ideas in confinement physics.

From the multi-award winning editorial team of G. Robert Odette (UCSB) and Steve Zinkle (ORNL), and with a contributor board drawn exclusively from the leaders of each alloy discipline, "Structural Alloys for Nuclear Energy Applications" instructs the current and next generations of researchers and industry staff on the behavior of steels and nickel-base alloys for nuclear energy applications. The book covers phenomenon including fatigue, deformation, and embrittlement, as well as materials topics such as advanced ODS steels, RAFM steels for fusion, computational design of nuclear structural materials, and much more.

Distilling valuable archival information for international researchers in the field of radiation effects on structural materials, this full-color reference is a critical resource for graduate students and institutional staff at this time of pivotal change in the nuclear industry.
Cross-referencing of critical phenomena marries generality of phenomena (e.g., void swelling) to specific material or applicationHundreds of citations provide references for further readingMore than 140 full-color figures, graphs, and sidebars

Dr. Samuel Glasstone, the senior author of the previous editions of this book, was anxious to live until his ninetieth birthday, but passed away in 1986, a few months short of this milestone. I am grateful for the many years of stimulation received during our association, and in preparing this edition have attempted to maintain his approach. Previous editions of this book were intended to serve as a text for students and a reference for practicing engineers. Emphasis was given to the broad perspective, particularly for topics important to reactor design and oper ation, with basic coverage provided in such supporting areas as neutronics, thermal-hydraulics, and materials. This, the Fourth Edition, was prepared with these same general objectives in mind. However, during the past three decades, the nuclear industry and university educational programs have matured considerably, presenting some challenges in meeting the objec tives of this book. Nuclear power reactors have become much more complex, with an ac companying growth in supporting technology. University programs now offer separate courses covering such basic topics as reactor physics, thermal hydraulics, and materials. Finally, the general availability of inexpensive xv xvi Preface powerful micro-and minicomputers has transformed design and analysis procedures so that sophisticated methods are now commonly used instead of earlier, more approximate approaches."

The clamor for non-carbon dioxide emitting energy production has directly impacted on the development of nuclear energy. As new nuclear plants are built, plans and designs are continually being developed to manage the range of challenging requirement and problems that nuclear plants face especially when managing the greatly increased operating temperatures, irradiation doses and extended design life spans. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments provides a comprehensive treatment of the structural materials for nuclear power plants with emphasis on advanced design concepts. Materials for Nuclear Plants: From Safe Design to Residual Life Assessments approaches structural materials with a systemic approach. Important components and materials currently in use as well as those which can be considered in future designs are detailed, whilst the damage mechanisms responsible for plant ageing are discussed and explained. Methodologies for materials characterization, materials modeling and advanced materials testing will be described including design code considerations and non-destructive evaluation concepts. Including models for simple system dynamic problems and knowledge of current nuclear power plants in operation, Materials for Nuclear Plants: From Safe Design to Residual Life Assessments is ideal for students studying postgraduate courses in Nuclear Engineering. Designers on courses for code development, such as ASME or ISO and nuclear authorities will also find this a useful reference.

Proceedings of the 3rd World Conference on [title] held in Osaka, Japan, May 1989. The 107 papers are arranged in 16 categories: reviews; reactor facilities; small source systems; detectors; film method; track-etch method; television method; image processing; real-time applications; nuclear applicat

Aimed primarily at operating organizations of nuclear power plants (NPPs) and regulatory bodies, this Safety Guide provides specific recommendations to ensure that operations in NPPs are conducted in a safe, effective, thorough and professional manner. It identifies the main responsibilities and operating practices in relation to such safe operation. The structure of the operations department, which is the part of the operating organization responsible for the conduct of operations of an NPP is addressed. Also addressed are the setting of high standards of performance and making safety related decisions in an effective manner, conducting control room activities in a thorough and professional manner and maintaining a nuclear power plant within the established operational limits and conditions.

This book attempts to look into the genesis of security culture as a concept which emerged with the recognition of the role of the human factor in the context of security. It traces the rapid evolution of security culture into a multi-functional discipline reinforced by supplementary tools such as assessment and enhancement methodologies, reviews practical steps to harmonize nuclear safety and security culture as well as recommends its practical application to address insider threats and their consequences. In addition, it demonstrates how to tailor the generic model of nuclear security culture to meet specific needs of diverse facilities and activities in different countries. Finally, the book discusses several challenges which need to be addressed to make security culture a user-friendly, universal, and sustainable instrument to turn the perception of the human factor as a liability into an asset of nuclear security.

This book covers the basic principles of both fusion and plasma physics, examining their combined application for driving controlled thermonuclear energy. The author begins by explaining the underlying scientific theory, and then goes on to explore the nuances of deployment within thermonuclear reactors. The potential for these technologies to help shape the new generation of clean energy is examined in-depth, encompassing perspectives both highlighting benefits, and warning of challenges associated with the nuclear fusion pathway. The associated computer code and numerical analysis are included in the book. No prior knowledge of plasma physics or fusion is required.

The Three Mile Island and Chernobyl nuclear incidents emphasized the need for the world-wide nuclear community to cooperate further and exchange the results of research in this field in the most open and effective manner. Recognizing the roles of heat and mass transfer in all aspects of fission-product behavior in sever reactor accidents, the Executive Committee of the International Centre for Heat and Mass Transfer organized a Seminar on Fission Product Transport Processes in Reactor Accidents. This book contains the eleven of the lectures and all the papers presented at the seminar along with four invited papers that were not presented and a summary of the closing session.

This thesis investigates the behavior of two candidate materials (a-SiO2 and MgO) for applications in fusion (e.g., the International Thermonuclear Experimental Reactor ITER) and Generation IV fission reactors. Both parts of the thesis - the development of the ionoluminescence technique and the study of the ion-irradiation effects on both materials - are highly relevant for the fields of the ion-beam analysis techniques and irradiation damage in materials. The research presented determines the microstructural changes at different length scales in these materials under ion irradiation. In particular, it studies the effect of the irradiation temperature using several advanced characterization techniques. It also provides much-needed insights into the use of these materials at elevated temperatures. Further, it discusses the development of the ion-beam-induced luminescence technique in different research facilities around the globe, a powerful in situ spectroscopic characterization method that until now was little known. Thanks to its relevance, rigorosity and quality, this thesis has received twoprestigious awards in Spain and France.

The surplus of plutonium in the world is both an important security issue, and a fact with implications for nuclear energy and environmental policy internationally. The two perspectives are inextricably intertwined in considering options for dealing with the plutonium surplus. It was for this reason that two research programmes at the Royal Institute of International Affairs - respectively on Energy and Environment, and on International Security - jointly approached NATO with a view to organising a work shop on the issue. It was most welcome then to learn that the NATO Science Programe was already supporting plans for a workshop on the issue, initiated by Richard Garwin, and we were pleased to accept the resulting invitation to host that workshop. DrGarwin prepared the initial agenda and established contacts and initial approaches to many of the participants; we were able to develop the agenda further and extend participation in some complementary ways. The result was a most lively and broad-ranging internation al and inter-disciplinary discussion. As the hosts, the RIIA was also given lead responsibility for producing the pro ceedings of the workshop as a publication for NATO. Many of the papers to the work shop are more technical than usually involved in a workshop at the Royal Institute. Yet this is an area in which the policy options are unusually dependent upon a good under standing of the technical issues. which themselves are often a matter of dispute."